ML20211G336

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Forwards Safety Evaluation Re 860221 Special Rept on Steam Generator Tube Denting Derived from 1985 Eddy Current Insp Data.Corrective Actions,Including Improving Secondary Chemistry Limits,Appropriate
ML20211G336
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/12/1987
From: Paulson W
Office of Nuclear Reactor Regulation
To: Andrews R
OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20211G341 List:
References
TAC-60913, NUDOCS 8702250351
Download: ML20211G336 (2)


Text

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3)B B oN FEB 121987

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Distribution Docket No. 50-285 Qocket Fils> PKreutzer NRC/ Local PDR WPaulson PBD8 Reading ACRS (10)

Mr. R. L. Andrews FMiraglia BGrimes Division Manager - Nuclear Production JPartlow EJordan Omaha Public Power District OGC-Beth NThompson 1623 Harney Street Gray File 3.3a Omaha, Nebraska 68102

Dear Mr. Andrews:

SUBJECT:

SPECIAL REPORT ON STEAM GENERATOR TUBE DENTING Re: Ft. Calhoun Station, Unit No. 1 The NRC staff has completed its review of the special report on steam generator tube denting submitted by your letter dated February 21, 1986. This report was derived from 1985 eddy current inspection data for the Fort Calhoun Station, Unit No. 1. The staff's safety evaluation is enclosed.

The staff finds that the data indicates that denting has progressed during the last cycle. The staff has reviewed a number of corrective actions taken by Omaha Public Power District (OPPD) and finds them appropriate. These actions include improving secondary chemistry limits; implementing a condenser integrity program; utilizing chemistry holdpoints during startups and shutdowns to flush contaminants from the secondary side; replacing feedwater heater tube bundles to reduce copper deposit levels in the SG; and implementing a boric acid treatment program for the secondary side to retard dent growth. The results of the 1987 examination will determine the effectiveness of the boric acid program and provide another data point for monitoring dent growth rates. The staff further concludes that the steam generators are acceptable for continued operation and that the subject report submitted by the OPPD has satisfied the requirements for reporting of eddy current testing results as stated in Technical Specifications 3.3(2)e(ii).

Sincerely,

. original signed by Walter A. Paulson, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B

Enclosure:

As stated cc w/ enclosure:

See next page PBD-8: PB PBD-8:

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Mr. R. L. Andrews Fort Calhoun Station Omaha Public Power District ~ Uni t-Nor --

cc:

Harry H. Voigt, Esq.

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C. 20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Phillip Harrell, Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations C-E Power Systems 7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Harold Borchert, Director Division of Radiological Health Department of Health 301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska 68509 l

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